Investigation of a steam generator tube rupture sequence using VICTORIA
- Sandia National Labs., Albuquerque, NM (United States)
- Nuclear Regulatory Commission, Washington, DC (United States)
VICTORIA-92 is a mechanistic computer code for analyzing fission product behavior within the reactor coolant system (RCS) during a severe reactor accident. It provides detailed predictions of the release of radionuclides and nonradioactive materials from the core and transport of these materials within the RCS. The modeling accounts for the chemical and aerosol processes that affect radionuclide behavior. Coupling of detailed chemistry and aerosol packages is a unique feature of VICTORIA; it allows exploration of phenomena involving deposition, revaporization, and re-entrainment that cannot be resolved with other codes. The purpose of this work is to determine the attenuation of fission products in the RCS and on the secondary side of the steam generator in an accident initiated by a steam generator tube rupture (SGTR). As a class, bypass sequences have been identified in NUREG-1150 as being risk dominant for the Surry and Sequoyah pressurized water reactor (PWR) plants.
- Research Organization:
- Sandia National Labs., Albuquerque, NM (United States)
- Sponsoring Organization:
- Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- AC04-94AL85000
- OSTI ID:
- 202438
- Report Number(s):
- SAND--95-2973C; CONF-9510156--4; ON: DE96003699
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
AEROSOLS
BUILDUP
CHEMICAL REACTIONS
FISSION PRODUCTS
HEAT TRANSFER
HYDRAULICS
NUCLEAR POWER PLANTS
RADIATION TRANSPORT
RADIOACTIVE EFFLUENTS
RADIONUCLIDE KINETICS
REACTOR ACCIDENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
RUPTURES
STEAM GENERATORS
SURRY-1 REACTOR
SURRY-2 REACTOR
SURRY-3 REACTOR
SURRY-4 REACTOR
TUBES
V CODES